ML061040007

NRC CY2005 Annual Assessment Meeting, Sequoyah Nuclear Plant, Soddy-Daisy, Tn, April 5, 2006

ML061040007
Person / Time
Site:	Sequoyah
Issue date:	04/05/2006
From:	NRC/RGN-II
To:
References
Download: ML061040007 (18)

Text

NRC CY2005 Annual Assessment Meeting Sequoyah Nuclear Plant Soddy-Daisy, TN April 5, 2006

Purpose of Todays Meeting A public forum for discussion of Sequoyah performance NRC will address Sequoyah performance issues identified in the annual assessment letter Sequoyah management will be given the opportunity to respond to the information in the letter and inform the NRC of new or existing programs to maintain or improve their performance

Agenda Introduction Review of Reactor Oversight Process (ROP)

National Summary of Plant Performance Discussion of Sequoyah Plant Performance Results Sequoyah Management Response and Remarks NRC Closing Remarks Break NRC Available to Address Public Questions

William Travers Regional Administrator Loren Plisco Deputy Regional Administrator Charles Casto Victor McCree Director Division of Reactor Projects Director Division of Reactor Safety Joseph Shea Harold Christensen Deputy Director Deputy Director Malcolm Widmann Regional Specialists Branch Chief Project Engineers Sequoyah Scott Shaeffer Resident Inspectors Larry Mellon Scott Freeman Larry Garner Mark Speck Heather Gepford

NRC Performance Goals PRIMARY GOALS Ensure protection of the public health and safety and the environment Ensure the secure use and management of radioactive materials OTHER GOALS

• Ensure openness in NRC regulatory process

• Ensure that NRC actions are effective, efficient, realistic, and timely

• Ensure excellence in NRC management to carry out the NRCs strategic objective

Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Threshold Threshold Action Matrix Regulatory Response

Examples of Baseline Inspections Equipment Alignment ~80 hrs/yr Triennial Fire Protection ~200 hrs every 3 yrs Operator Response ~125 hrs/yr Emergency Preparedness ~80 hrs/yr Rad Release Controls ~110 hrs every 2 yrs Worker Radiation Protection ~90 hrs/yr Corrective Action Program ~250 hrs every 2 yrs Corrective Action Case Reviews ~60 hrs/yr

Performance Thresholds Safety Significance Green: Very low safety issue White: Low-to-moderate safety issue Yellow: Substantial safety issue Red: High safety issue NRC Inspection Efforts Green: Only Baseline Inspections White: May increase NRC oversight Yellow: Increased NRC oversight Red: Increased NRC oversight and other NRC actions

Action Matrix Concept Licensee Regulatory Degraded Multiple/Rep. Unacceptable Response Response Cornerstone Degraded Performance Cornerstone ncreasing Safety Significance ncreasing NRC Inspection Efforts ncreasing NRC/Licensee Management Involvement ncreasing Regulatory Actions

National Summary of Plant Performance Status at End of CY 2005 icensee Response 84 egulatory Response 12 egraded Cornerstone 4 ultiple/Repetitive Degraded Cornerstone 3 nacceptable 0 Total 103

Sequoyah CY2005 Inspection Activities 3200 hours0.037 days <br />0.889 hours <br />0.00529 weeks <br />0.00122 months <br /> of inspection related activities, including:

• Problem identification and resolution inspection

• Radiation protection inspections

• Safety system design and performance inspection

• Fire protection inspection

• ISFSI operations inspection

• Heat sink inspection

• Engineering modification inspection

• Emergency preparedness inspections

• Reactor operator initial exam

• Unit 2 outage-related in-service inspections

• Supplemental inspection for one White finding in a strategic performance area (95001)

Sequoyah CY2005 Assessment Results

• Both Units performance was within the Licensee Response Column of the NRCs Action Matrix.

• All Unit 1 & 2 inspection findings were classified as very low safety significance (Green).

• All Unit 1 & 2 performance indicators were Green

Sequoyah Annual Assessment Summary TVA operated Sequoyah in a manner that preserved public health and safety All cornerstone objectives were met NRC plans baseline inspections at Sequoyah for the remainder of CY 2006 as well as routine ISFSI inspections.

Sequoyah CY2006 Scheduled Inspection Activities

• Resident inspector daily inspections

• Radiation protection inspections

• Emergency preparedness inspections

• Licensed operator requalification inspection

• ISFSI operations inspection

• Maintenance inspection

• Engineering modification inspection

• Unit 1 & 2 outage-related inservice inspections

• Unit 2 Reactor Pressure Vessel Head and Penetration Nozzle inspections

• Unit 2 PWR containment sump blockage inspection

NRC CY2005 Annual Assessment Meeting Sequoyah Nuclear Plant Soddy-Daisy, TN April 5, 2006

Contacting the NRC Report an emergency (301) 816-5100 (call collect)

Report a safety concern:

(800) 695-7403 Allegation@nrc.gov General information or questions www.nrc.gov Select What We Do for Public Affairs

Reference Sources Reactor Oversight Process http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html Public Electronic Reading Room http://www.nrc.gov/reading-rm.html Public Document Room 1-800-397-4209 (Toll Free)

Sequoyah Attendance List April 5, 2006 Licensee Personnel

• Kay Whittenburg, TVA

• Tom Niessen, TVA

• Jim Smith, TVA

• Kevin Wilkes, TVA

• David Kulisek, TVA

• Randy Douet, TVA

• Mark Palmer, TVA

• Rick Rogers, TVA NRC Personnel

• Malcolm Widmann, DRP

• Scott Freeman, DRP

• Mark Speck, DRP

• Roy Hickok, NRC Public Attendees

• Ken Newhart